ML20195J752

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Rev 7 to Jaf Colr
ML20195J752
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 11/18/1998
From: Rodriquez F
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20195J750 List:
References
NUDOCS 9811250059
Download: ML20195J752 (33)


Text

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 7 REVIEWED BY: PLANT OPERATIONS REVIEW COMMITTEE MEETING NO. 78 -033 DATE II//7!T8 APPROVED BY: Francisco Rodrip DATE U~~I8'98 REACTOR ANALYST S%RVfSOR APPROVED BY DATE Il- 12 -9I

( SITE EXEClfDIVE OFFICER UEKEL_D wv Va 1 e KO!bbb$33 em (3

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_, ' CORE OPERATING LIMITS REPORT CYCLE 14 1.0 - PURPOSE This report provides the cycle-specific operating limits for Cycle 14 of the James A.

FitzPatrick Nuclear Power Plant. The following limits are addressed:

Operating Limit Minimum Critical Power Ratio (MCPR)

Flow Dependent MCPR Limits Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Linear Heat Generation Rate (LHGR)

Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)

Settings -

Stability Option ID Exclusion Region 2.0 APPLICABILITY ,

i n The plant shall be operated within the limits specified in this report. If any of these

-(/ limits are violated, the corrective actions specified in the Technical Specifications shall be taken.

3.0 REFERENCES

3.1 JAFNPP Administrative Procedure 12.05, Control of Core Operating Limits Report.

3.2 JAFNPP License Appendix A, Operating Technical Specifications.

3.3 FitzPatrick Cycle 14 Core Reload Safety Evaluation, JAF-SE-98-006.

3.4 - GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 13 Cycle 14, J11-03359SRL, Rev.1, October 1998 3.5 GE Report, Supplemental Reload Licensing Repon for James A. FitzPatrick Reload 12 Cycle 13,J11-02914SRL Rev.0, August 1996 3.6' GE Report, Supplemental Reload Licensing Repon for James A. FitzPatrick Reload 11

' Cycle 12,24A5167, Rev.1, June 1996 3.7 GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 10 Cycle 11,23A7114, Rev.1, July 1992 3.8 ' Cycle 14 Core Reload, M197-030 Rev. No.' 7 Page 2 of 33

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  • CORE OPERATING LIMITS REPORT CYCLE 14 3.9 - RAP-7.3.17, Core Monitoring Software and Database Changes.

l 3.10 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035. i l

3.11 James A. FitzPatrick Nuclear Power Plant K, Curve Update, GE-NE-J11-03426-00-01, September 1998. I I

3.12 FitrPatrick Cycle 12 Core Reload Safety Evaluation, JAF-SE-94-127. I 3.13 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-13 3.14 James A. FitzPatrick ATRIUM-10A Lead Fuel Assembly Safety Analysis Report, EMF-94-141(P), November,1994 3.15 GE Letter,J. Baumganner to P. Lemberg, Exposure Dependent LHGR Limit Curves, JAB-N8076, November 5,1998.

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' 3.16 GE Supplement 1 to Supplemental Reload Licensing Report for James A. FitzPatrick Reload 10 Cycle 11,23A7114AA, Rev.0, June 1992 j 3.17 GE Lattice Dependent MAPLHGR Report for James A. FitzPatrick Nuclear Power Plant, Reload 11 Cycle 12,24A5167AA, Rev.0, December 1994.

3.18 GE Lattice Dependent MAPLHGR Report for James A. FitzPatrick, Reload 12 l i

Cycle 13,J11-02914 MAP, Rev. O, August 1996.

j 3.19 GE Lattice Dependent MAPLHGR Report for James A. FitzPatrick, Reload 13, l Cycle 14,.J11-03359 MAPL, Rev. O, October 1998. i l

4.0 DEFINITIONS I

4.1 Minimum critical power ratio (MCPR) - Minimum value of the ratio of that power in a fuel assembly which is calculated to cause some point in that fuel assembly to experience boiling transition to the actual assembly operating power as calculated by -

application of the GEXL correlation (Reference NEDE-10958).

l 4.2 Fraction of Limiting Power Density - The ratio of the linear heat generation rate

(LHGR) existing at a given location to the design LHGR. The design LHGR is given l

in Table 8.2.

4.3 Maximum Fraction of Limiting Power Density - The Maximum Fraction of Limiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Limiting Power Density (FLPD).

4.4 Rated Recirculation Flow - that drive flow, which produces a core flow of 77.0 x 10' lb/hr.

Rev. No. 7 Page 3 of 33

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  • CORE OPERATING LIMITS REPORT CYCLE 14 D

.' 5.0 - RESPONSIBILITIES 5.1 See AP-12.05 (Reference 3.1).

5.2 It is the responsibility of the Shift Manager to assure that the reactor is operated veithin the limits described herein.

5.3 It is the responsibility of the Reactor Analyst Supervisor to assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.9) 6.0 SPECIAL INSTRUCTIONS /REOUIREMENTS Not applicable.

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I Rev. No. 7 Page 4 of 33 i

- CORE OPERATING LIMITS REPORT CYCLE 14 f3 g 7.0 , PROCEDURE 7.1 Operating Limit MCPR

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During power operation, The Operating Limit MCPR shall be equal to or greater than the limits given below.

7.1.1 Technical Specification

Reference:

3.1.B 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:

7.1.2.1 The average scram time to notch position 38 shall be:

TAVE 5T B 7.1.2.2 The average scram time to notch position 38 is determined as follows: l n

E Nire r az = '~',,

1 where:

n- number of surveillance tests performed to date in the cycle, N, - number of active rods measured in the surveillance i j l

T, - average scram time to notch position 38 of all rods measured in surveillance test i.

7.1.2.3 The adjusted analysis mean scram time is calculated as follows:  ;

l

+ -

U2 N l vg (sec)= p + 1.650- ,,' l EN: l l .i=1 .

where:

- mean of the distribution for the average scram insertion time to O

'y/

the pickup of notch position 38 - 0.706 sec.

o- standard deviation of the distribution for average scram

! Rev. No. 7 Page 5 of 33 I .

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, ' CORE OPERATING LIMITS REPORT CYCLE 14 insenion time to the pickup of notch position 38 - 0.016 sec.

N i- the total number of active rods measured in Technical Specification 4.3.C.1.

l The number of rods to be scram tested and the test intervals are given in Technical Specification 4.3.C.

L .7.1.3 . When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, or Table 8.1.A if operating above 75% of rated thermal power with three steam lines in service.

7.1.4 When the requirement 7.1.2.1 is not met (i.e. t 3 < t avg) then the .

l- Operating Limit MCPR values (as a function of T) are given in Figure 8.1, or Figure 8.1.A if operating above 75% of rated thermal power with three steam lines in service.

Where: T - (tave-t V(t3 3 - Ts) and T3yg - the average scram time to notch position 38 as defined in l

i 7.1.2.2.

ta -

the adjusted analysis mean scram time as defined in 7.1.2.3 l T3 the scram time to notch position 38 as defined in Technical Specification 3.3.C.1.

NOTE: Should the operating limit MCPR obtained from these figures be less than the operating limit MCPR found in 7.1.3 then 7.1.3 shall SPPY- l S 7.1.5 During single-loop operation, the Operating Limit MCPR shall be I

! increased by 0.01.

l 7.1.6 During reactor power operation with core flow less than 100 percent of

)

rated, the Operating Limit MCPR shall be multiplied by the appropriate  ;

Kr specified in Figure 8.2.

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l Rev. No. 7 Page 6 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 i

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) 7.2 - Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 7.2.1 Technical Specification

Reference:

3.5.H l

l 7.2.2 During power operation, the APLHGR for each fuel type as a function of axial location and average planar exposure shall be within limits based on applicable APLHGR limit values which have been approved for the respective fuel and lattice types.

l l 7.2.3 When hand calculations are required, the APLHGR for each type of fuel l as a function of average planar exposure shall not exceed the limiting l value for the most limiting lattice shown in Figures 8.3.A through G.

7.2.4 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 or 7.2.3 above multiplied by the appropriate values (0.76 and 0.78 for GE11 and GE12, respectively).

7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification

Reference:

3.5.I.

'^ 7.3.2 During power operation, the LHGR for each fuel type as a function of l axial location and average planar exposure shall be within limits based on applicable LHGR limit values which have been approved for the I respective fuel and lattice types. l 7.3.3 When hand calculations are required, the LHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice as specified in Table 8.2 and shown in Figure 8.5.

7.4 APRM Trip Settings ,

7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) 7.4.1.1 Technical Specification

References:

2.1.A.1.c, Table 3.1-1,3.1.A l

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l Rev. No. 7 Page 7 of 33

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, CORE OPERATING LIMITS REPORT - CYCLE 14

'O V , 7.4.1.2 When the Mode Switch is in the RUN position, the APRM flow referenced flux scram trip setting shall be:

S10.66W + 54% for two loop operation; S10.66W + 54% - 0.66 AW for single loop operation; where:

S- setting in percent of rated thermal power; W- recirculation flow in percent of rated; AW - difference between two loop and single-loop effective drive flow at the same core flow.

7.4.1.3 In the event of operation with a maximum fraction oflimiting power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows:

S1(0.66W + 54%)(FRP/MFLPD) for two loop operation; S1(0.66W + 54% - 0.66 AW)(FRP/MFLPD) for single-loop operation; where:

FRP - fraction of rated thermal power;

MFLPD - Maximum fraction of limiting power density, see Definition 4.3.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

O Rev. No. 7 Page 8 of 33

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. " ~ CORE OPERATING LIMITS REPORT CYCLE 14 7.4.2 APRM Flow Biased Rod Block Setting 7.4.2.1 Technical Specification

References:

2.1.A.1.d, Table 3.2-3,3.2.C 7A.2.2 The APRM rod block trip setting shall be:

S10.66W + 42% for two loop operation; i

l S10.66W + 42% - 0.66 AW for single loop operation; where:

l. 'S- rod block setting in percent of rated thermal power; W- recirculation flow in percent of rated; AW - difference between two loop and single loop effective drive flow l at the same core flow.

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7A.2.3 In the event of operation with a maximum fraction oflimiting power ,

density (MFLPD) greater than the fraction of rated power (FRP), the O

lb-l setting shall be modified as follows:

Si(0.66W + 42%)(FRP/MFLPD) for two loop operation; i

S1(0.66W + 42% - 0.66AW)(FRP/MFLPD) for single loop operation; where:

FRP - fraction of rated thermal power; MFLPD - maximum fraction of limiting power density, l Definition 4.3 )

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Rev. No. 7 Page 9 of 33 i . .

l', CORE OPERATING LIMITS REPORT CYCLE 14

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l. 7.5 RBM Flow Biased Rod Block Setting l

7.5.1 Technical Specification

Reference:

3.2.C 7.5.2 The RBM flow biased rod block trip setting shall be:

S10.66W + K for two loop operation; S10.66W + K - 0.66AW for single loop operation; where:

S - rod block setting in percent of initial; W - loop flow in percent of rated K - intercept values of 39%,40%,41%,42%,43%, and 44% can be used with the appropriate MCPR Operating Limit from Table 8.1(note that for Cycle 14 the RBM intercept value does not effect the MCPR l Operating Limit for K values s 44%);

AW - difference between two loop and single loop effective drive flow at i i the same core flow.

1 7.5 Stability Option 1-D Exclusion Region and Buffer Zone.

7.6.1 Technical Specification Reference 3.5.J l

! l 7.6.2 The reactor shall not be intentionally operated within the Exclusion  ;

, Region given in Figure 8.4 when the SOLOMON Code is operable. j 1

7.6.3 The reactor shall not be intenh.olly operated within the Buffer Zone given in Figure 8.4 when the SOL .) MON Code is inoperable 1

.O Rev. No. 7 Page 10 of 33

, CORE OPERATING LIMITS REPORT CYCLE 14 i

( - 7.7 K,- Flow Dependent MCPR Limit ls Figure 8.2 is the Kr limit. Values i of K are obtained using the following equatio i Reference 3.11):

! t Kr - MAX [1.0, A - SLOPE *WT]

l l

where:

WT - Core Flow as % of Rated,30% s WT s 100% '

SLOPE - ( Ar/100/OLMCPR ) * ( SLMCPR/SLMCPR ,,,,.,,)

^

A - ( B,/OLMCPR ) * ( SLMCPR/SLMCPRyo,.,

)

SLMCPR ,,,,,,. - 1.07 1

l SLMCPR - Technical Specification Reference 1.1.A t

i OLMCPR - the highest value obtained from Figures 8.1, and 8.1.A as per 7.1.4, or, j if the note in 7.1.4 applies, then 7.1.3 requirement must be met.

Ay , By - Coefficients for the K, curve listed below:

i-L Scoop Tube Serpoint % A, By 102.5 0.571

! 1.655  ;

107.0 0.586 1.697 '

112.0 0.602 1.747 117.0 0.632 1.809 All coefficients apply to Manual Flow Control Mode I

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!O Rev, No. 7 Page 11 of 33

, CORE OPERATING LIMITS REPORT CYCLE 14 8.0 . ' FIGURES AND TABLES l

Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.2 Maximum LHGR 1

1 Figure 8.1. MCPR Operating Limit Versus t for All Fuel Types Figure 8.1.A. MCPR Operating Limit Versus t for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for All Fuel Types Figure 8.2 K, Factor Figure 8.3.A MAPLHGR versus Planar Average Exposure:

GE11-P9 HUB 359-16GZ1-100M-146-T l Figure 8.3.B MAPLHGR versus Planar Average Exposure:

I GE11 P9 HUB 356-15GZ-100M-146-T and ATRIUM-10A Figure 8.3.C MAPLHGR versus Planar Average Exposure:

GE11-P9 HUB 380-12GZ5-100M-146-T Figure 8.3.D MAPLHGR versus Planar Average Exposure:

GE12-P10DSB417-15GZ-100T-150-T l Figure 8.3.E MAPLHGR versus Planar. Average Exposure:

GE12-P10DSB412-17GZ-100T-150-T l

l Figure 8.3.F MAPLHGR versus Planar Average Exposure:

GE 12-P10DSB407-14G6.0-100T-150-T l

Figure 8.3.G MAPLHGR versus Planar Average Exposure: l GE12-P10DSB407-17GZ-100T-150-T l l

Figure 8.4 Stability Option 1D Exclusion Region

. Figure 8.5, Exposure Dependent LHGR Limit for Gell and GE12 fuel.
() .

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Rev. No. 7 Page 12 of 33 l

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. CORE OPERATING LIMITS REPORT CYCLE 14 s.

FIGURE 8.6.A Cycle 14 Loading Pattern, Upper Left Quadrant, Bundle Design FIGURE 8.6.B Cycle 14 Loading Pattern, Upper Right Quadrant, Bundle Design FIGURE 8.6.C Cycle 14 Loading Pattern, Lower Right Quadrant, Bundle Design FIGURE 8.6.D Cycle 14 Loading Pattern, Lower Left Quadrant, Bundle Design l

FIGURE 8.7 Users Guide 9.0 EXHIBITS Not Applicable.

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Rev. No. 7 Page 13 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 i

TABLE 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Cycle 14 ALL Exposure Range BOC 1.34 to 10 GWD/ST -

> 10 GWD/ST 1.39 to EOC  !

Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

See Reference 3.3 and 3.14 for MCPR requirement for ATRIUM 10A assemblies, required margin is provided by non-limiting core locations.

NOTE: When entering a new Exposure Range, check the current value of T to assure adjustment per Section 7.1.4 NOTE: Applicable for values of K s 44%, see section 7.5.2 l

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d Rev. No. 7 Page 14 of 33

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CORE OPERATING LIMITS REPORT: CYCLE 14' s

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TABLE 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Cycle 14 ALL Exposure Range BOC 1.36 to 10 GWD/ST -

> 10 GWD/ST 1.41 to EOC Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

See Reference 3.3 and 3.14 for MCPR requirement for ATRIUM-10A assemblies, required margin is provided by non-limiting core locations.

NOTE: When entering a new Exposure Range, check the current value of T to assure adjustment per Section 7.1.4 NOTE: Applicable for values of K s 44%, see section 7.5.2 O

Rev. No. 7 Page15of33

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. CORE OPERATING LIMITS REPORT CYCLE 14 l

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TABLE 8.2 l Maximum LHGR Fuel Type Fuel Bundle Design Maximum LHGR (kW/ft)

GE11-P9 HUB 356-15GZ-100M-146-T GE11 See Figure 8.5 GE11 P9 HUB 359-16GZ1-100M-146-T GE11-P9 HUB 380-12GZ5-100M-146-T .

GE12-P10DSB417-15GZ-100T-150-T GE12 See Figure 8.5 ,

GE12-P10DSB412-17GZ-100T-150-T '

GE12-P10DSB407-17GZ-100T-150-T GE12-P10DSB407-14G6.0-100T-150-T ,

i Technical Specification

Reference:

3.5.I J

! L Design features of the fuel assemblies in the Cycle 14 core are provided in Reference 3.8 LHGR for ATRIUM-10A assemblies is controlled by the MAPLHGR limit given in Figure 8.3.B see Reference 3.12 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.

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Rev. No. 7 Page 16 of 33

. CORE OPERATING LIMITS REPORT - CYCLE 14 1

FIGURE 8.1  !

MCPR Operating Limit Versus t for l All Fuel Types 1.48

-+-BOC to 10 GWD/ST A I i 47

~

- B - > 10 GWD/ST to EOC ,-

E 1 .44 ',,'#

N 1..;I . -

~

y' > 1.39 1 38 1-39 1.3e -

I 1.34 <

1,34 1.32 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

(

x T Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

NOTE: Should the operating limit MCPR obtai . d from this figure be less than the operating limit MCPR found in 7.1.3 for the appliu, vie RBM trip level setting then 7.1.3 shall apply.

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O Rev. No. 7 Page 17 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 l ' -

FIGURE 8.1.A l MCPR Operating Limit Versus T For Operation above 75% of Rated Thermal Power with Three Steam Lines in Service For All Fuel Types l 1.5

BOcto 10 GNDfST ,# l 40

_ .e_ _ > 10 GN0fST to 80C ,, '  ;

1.46 ,-

, a. '

l 1,44 .

1.42 ,

~j P , 1.41 1.4 -n1.41 1 1.38 ..._

1.36 ,

[1.36 1.34 0 0.2 0.4 0.6 0.8 1 T

Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

NOTE: Should the operating limit MCPR obtained from this figure be less than the l p operating limit MCPR found in 7.1.3 for the applicable RBM trip level setting then 7.1.3 shall l 2PPlY-L l l

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I l- . Rev. No. 7 Page 18 of 33 l'

CORE OPERATING LIMITS REPORT CYCLE 14 FIGURE 8.2 K, Factor Scoop Tube Setpoint of 102.5 1.25 For BOC to 10 GWD/ST 1.20 A  !  !  !

'For > 10 GWD/ST 1.15 E 1.10 l 1.05 l

1.00 51 ,345 59.863 l l

' l 0.95 '

30 40 50 60 70 80 90 100 WT, % Rated Core Flow On L.)

Technical Specification

Reference:

3.1.B See Section 7.7 NOTE: K, for Single Loop Operation is slightly greater than for Dual Loop Operation limits. Therefore, Kr calculated for Single Loop Operation is more conservative and will be applied to Dual Loop Operation as well..

SLMCPR - 1.10 (SLO)

OLMCPR - 1.35 for BOC to 10 GWD/ST (SLO) 1.40 for > 10 GWD/ST (SLO)

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Rev. No. 7 Page 19 of 33

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, CORE OPERATING LIMITS REPORT CYCLE 14 f3 O -

FIGURE 8.3.A l MAPLHGR versus Planar Average Exposure:

l GE11-P9 HUB 359-16GZ1-100M-146 T

( )

14 12

^ 10 I- e a

e i 36 n.

l4 2

0 ,

0 10 20 30 40 50 60 Raner Average Fe=e(CMENST)

% )

This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.7and 3.16.

Technical Specification

Reference:

3.5.H For single loop operation these MAPLHGR values shall be multiplied by 0.76.

O Rev. No. 7 Page 20 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 FIGURE 8.3.B MAPLHGR versus Planar Average Exposure:  ;

GE11-P9 HUB 356-15GZ-100M-146-T and ATRIUM-10A I

~

r y 1 14 12 10 l

p8 6

n.

$4 2

0+ , ,

0 10 20 30 40 50 60 maner Average Furw==e (GNYST)  !

< J l O

The ATRIUM-10A bundles will be monitored as a GE11-P9 HUB 356-15GZ-100M-146-T bundle. Operation to the limiting MAPLHGR for the GE11 bundle assures this bundle will remain within LHGR limits, see Reference 3.12.

This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.7and 3.16.

Technical Specification

Reference:

3.5.H For single loop operation these MAPLHGR values shall be multiplied by 0.76.

O Rev. No. 7 Page 21 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 t

FIGURE 8.3.C MAPLHGR versus Planar Average Exposure:

GE11-P9 HUB 380-12GZ5-100M-146-T

( h 14 12 10 I E*

E 6 -

t

'l 4 -

2 0I . , , , ,

0 10 20 30 40 50 60 Planar Average Exposure (GWDfST) x J This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.6 and 3.17.

For single loop operation these MAPLHGR values shall be multiplied by 0.76.

Technical Specification

Reference:

3.5.H O

Rev. No. 7 Page 22 of 33

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. CORE OPERATING LIMITS REPORT CYCLE 14 9

  • FIGURE 8.3.D MAPLHGR versus Planar Average Exposure:

GE12-P10DSB417-15GZ-100T-150-T f h 12 10 -

l 1* [

i g 6--

i

  • i 2

0 0 10 20 30 40 50 60 Planar Average Exposure (GMDST)

)

O

(

This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.5 and 3.18.

Technical Specification

Reference:

3.5.H

Reference:

23A7114 Rev 1 -

For single loop operation these MAPLHGR values shall be multiplied by 0.78.

Rev. No. 7 Page 23 of 33

. CORE OPERATING LIMITS REPORT CYCLE 14 i fM V .

FIGURE 8.3.E l MAPLHGR versus Planar Average Exposure: j GE12-P10DSB412-17GZ-100T-150-T I T 12 l

10 J i

I*,

l 5*

E l

I t*

b 2

0 ,

0 10 20 30 40 50 60 Manar Average Fura ==e (GWDfST)

(L J j O

i This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.5 and 3.18.

Technical Specification Peference: 3.5.H

Reference:

24A5167 Rev. 0 l For single loop operation these MAPLHGR values shall be multiplied by 0.78.

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Rev. No. 7 Page 24 of 33

CORE OPERATING LIMITS REPORT CYCLE 14 FIGURE 8.3.F MAPLHGR versus Planar Average Exposure:

GE12-P10DSB407-14G6.0-100T-150-T -

f 3 12 i 10 ~

I_ *

$6 z

d '

g4 -

2 -

0 ,

0 10 20 30 40 50 60 Renar Average Exposure (GADST) m  % )

This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.4 and 3.19.

Technical Specification

Reference:

3.5.H For single loop operation these MAPLHGR values shall be multiplied by 0.78.

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f Rev. No. 7 Page 25 of 33 I

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. CORE OPERATING LIMITS REPORT CYCLE 14 I i

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FIGURE 8.3G MAPLHGR versus Planar Average Exposure:

GE12-P10DSB407-17GZ-100T-150-T l

( ) i 12 l 10 1_*

~

g4 -

2 --

0 ,

0 10 20 30 40 50 60 Planar Average Furamare (GWLYST)

( I l

This curve represents the limiting exposure dependent MAPLHGR values per Reference 3.4 and 3.19.

Technical Specification

Reference:

3.5.H For single loop operation these MAPLHGR values shall be multiplied by 0.78.

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Rev. No. 7 Page 26 of 33

CORE OPERATING LIMITS REPORT CYCLE 14 C\

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Figure 8.4 Stability Option 1-D Exclusion Region 4

Power- Flow Map Showing Showing  ;

Exclusion Region Boundary and Buffer Zone Boundary 100 l

Buffer Zone Bounc ary 90  %-

Exclusion Region Bound 80 - N! x

/

70 / '

8

/

,4 '

, (-

gg / 7 i V ,;

u) @

50 -

! N*

, ,J.

g o l" " ',,, . . .

y 40 .I.

ad' 1 tg E

I

,1 30 - --J /

20 ,/

/ p)

/s' 10 - /

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20 25 30 35 40 45 50 1

Core Flow, % l a

Technical Specification Reference 3.5.J

,O Reference 3.11

%]

Rev. No. 7 Page 27 of 33

.- - . - . - - . - - - - - - . . - - _ . .. .-...- = - - . -.

l

. CORE OPERATING LIMITS REPORT CYCLE 14 FIGURE 8.5 Exposure Dependent LHGR Limit for GEli and GE12 Fuel 16

'4 ~

-._ GE11 12 m -* GE12 10 x

8-6 C 10 20 30 40 50 60 '

4 GWDIST Technical Specification

Reference:

3.5.I This curve represents the limiting exposure dependent LHGR values per Reference 3.15 Design features of the fuel assemblies in the Cycle 14 core are provided in Reference 3.8 LHGR for ATRIUM-10A assemblies is controlled by the MAPLHGR limit given in Figure 8.3.B see Reference 3.12 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.

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- . _ _ . . - . - - - . - - _ _ _ ~ . . - - . _ . _ . - . - . - .

. CORE OPERATING LIMITS REPORT CYCLE 14 l

FIGURE 8.5A  !

Cycle 14 Loading Pattern, Upper Left Quadrant, Bundle Design  ;

N4 A A A A A 52 l

from above A B B A B B 50 '

the core A A A B B B B B B 48 C B B B B B B B B B 46 )

A B A B B B B B B A B 44 l A B B B B B A B B B A 42 I l

A B B B B A B A B B B 40 A B B B B A B A B B B A 38 A B B B B A B A B B B A B 36 A B B B B B A B B A B B A 34 A A B ~B B B B B B B B A B 32 A B B B A B B B A B A B B 30 l A B B B B A B A B A B B A 28 1 3 5 7 9 11 13 15 17 19 21 23 25 A- GE11 B- GE12 C- ATRIUM - 10A O

l l

Rev. No. 7 Page 29 of 33 i

\

~

. CORE OPERATING LIMITS REPORT CYCLE 14 L

fM FIGURE 8.6.B Cycle 14 Loading Pattern, Upper Right Quadrant, Bundle Design A A A A A N4 52 B B A B B A from above the 50 core B B B B B B A A A 48 B B B B B B B B B C ~46 i

B A B B B B B B A A A 44 A B B B A B B B B B A 42 B B B A B A B B B B A 40 l A B B B A B A B B B B A 38

( B A B B B A B A B B B B A 36 A B B A B B A B B B B B A 34 B A B B B B B B B B B A A 32 B B A B A B B B A B B B A 30 A B B A B A B A B B B B A 28 27 29 31 33 35 37 39 41 43 45 47 49 51 i

A- Gell B- GE12 C- ATRIUM - 10A O

(_./

i i

l I

, Rev. No. 7 Page 30 of 33

CORE OPERATING LIMfrS REPORT CYCLE 14 4

FIGURE 8.6.C Cycle 14 Loading Pattern, Lower Right Quadrant, Bundle Design A B B A B A B A B B B B A 26 B B A B A B B B A B B B A 24 B A B B B B B B B B B A A 22 A B B A B B A B B B B B A 20 B A B B B A B A B B B B A 18 A B B B A B A B B B B A 16 B B B A B A B B B B A 14 A B B B A B B B B B A 12 j

B A B B B B B B A B A 10 B B B B B B B B B C 8 l

B B B B B B A A A 6  !

! l B B A B B A N4 4 A A A A A from above 2 the core 27 29 31 33 35 37 39 41 43 45 47 49 51 A- GEli B- GE12 C- ATRIUM - 10A O

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l l ~

CORE OPERATING LIMITS REPORT CYCLE 14 iG U -

FIGURE 8.6.D Cycle 14 Loading Pattern, Lower Left Quadrant, Bundle Design A B B B B A B A B A B B A 26 l

A B B B A B B B A B A B B 24 A A B B B B B B B B B A B 22 A B B B B B A B B A B B A '20 i

i A B B B B A B A B B B A B 18 i

A B B B B A B A 3 B B A 16

)

i A B B B B A B A B B B 14 A B B B B B A B B B A 12 A A A B B B B B B A B 10 l

C B B B B B B B B B 8 A A A B B B B B B 6 N4 A B B A B B 4

, from above A A A A A 2 l~ the core

( 1 3 5 7 9 11 13 15 17 19 21 23 25 l

A- GE11 B- GE12 C- ATRIUM - 10A l

i i

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. . . - - .. _ - -. . . .= = .

1' j- CORE OPERATING LIMITS REPORT CYCLE 14 l

l(VD l -

FIGURE 8.7 l USERS GUIDE l The COLR defines thermal limits for the various operating conditions expected during the l cycle. At the start of the cycle the 3D-Monicore databank contains limits for; e Cycle exposure range of BOC to $10 GWD/ST i

e t-0 e ' Dual recirculation pump operation, and

. Four steam line operation The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.

Change in Operating State Change in Limits Procedure Reference Cycle Exposure - 10 See Table 8.1(8.1.A for 3SL) or GWD/ST Figure 8.1 for t

  • 0(8.1.A for 3SL) None for change in MCPR.

, OLMCPR changes to EOC values Krlimit may be changed in

,(vj at cycle exposure of 10 GWD/ST recognition of higher OLMCPR.

Scram Time Test Results such Use new t and see Figure 8.1 or that t

  • 0 8.1.A for 3SL. Kr limit may be RAP-7.4.1 changed in recognition of higher Option B limits for OLMCPR OLMCPR.

must be interpolated with Option A limits Single Loop Operation Increase MCPR Limits by 0.01, or change acceptance criterion in ST-SE RAP-7.4.2, The SLMCPR increases by 0.01 to 0.99. K, does not change. ST-5E, and therefore OLMCPR limits Verify that 3D-Monicore has RAP-7.3.25 increase by 0.01. MAPLHGR is recognized the idle recirculation reduced by a multiplierin SLO.

loop and is applying the SLO MAPLHGR multipliers,0.76 for Gell, and 0.78 for GE12.

Three Steam Line Operation Increase OLMCPR according to (3SL) Table 8.1.A or Figure 8.1.A(t

  • 0). None Krlimit may be changed in

! OLMCPR values increase by 0.02 recognition of higher OLMCPR.

when operating on 3SL V

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